24 research outputs found

    Cross sections and isomeric cross-section ratios in the interactions of fast neutrons with isotopes of mercury

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    Excitation functions were measured for the reactions Hg-196(n, 2n)Hg-195(m,g),Hg-198(n, 2n)Hg-197(m,g),Hg-204(n, 2n)Hg-203,Hg-198(n,p)Au-198(g), and Hg-199(n,p)Au-199 over the neutron energy range of 7.6-12.5 MeV. Quasimonoenergetic neutrons were produced via the H-2(d,n)He-3 reaction using a deuterium gas target at the Julich variable energy compact cyclotron CV 28. Use was made of the activation technique in combination with high-resolution, high-purity Ge detector gamma-ray spectroscopy. All the data were measured for the first time over the investigated energy range. The transition from the present low-energy data to the literature data around 14 MeV is generally good. Nuclear model calculations using the codes STAPRE and EMPIRE-2.19, which employ the statistical and precompound model formalisms, were undertaken to describe the formation of both the isomeric and ground states of the products. The total reaction cross section of a particular channel is reproduced fairly well by the model calculations, with STAPRE giving slightly better results. Regarding the isomeric cross sections, the agreement between the experiment and theory is only in approximate terms. A description of the isomeric cross-section ratio by the model was possible only with a very low value of eta, i.e., the Theta(eff)/Theta(rig) ratio

    2nd Conference on Nuclear and Particle Physics

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    Excitation functions of proton-induced reactions on natFe and enriched 57Fe with particular reference to production of 57Co

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    Excitation functions of the reactions (nat)Fe(p,xn)(55,56,57,58)Co, (nat)Fe(p,x)(51)Cr, (nat)Fe(p,x)(54)Mn, (57)Fe(p,n)(57)Co and (57)Fe(p,alpha)(54)Mn were measured from their respective thresholds up to 18.5MeV, with particular emphasis on data for the production of the radionuclide (57)Co (T(1/2)=271.8d). The conventional stacked-foil technique was used, and the samples for irradiation were prepared by an electroplating or sedimentation process. The measured excitation curves were compared with the data available in the literature as well as with results of nuclear model calculations. From the experimental data, the theoretical yields of the investigated radionuclides were calculated as a function of the proton energy. Over the energy range E(p)=15-->5MeV the calculated yield of (57)Co from the (57)Fe(p,n)(57)Co process amounts to 1.2MBq/microAh and from the (nat)Fe(p,xn)(57)Co reaction to 0.025MBq/microAh. The radionuclidic impurity levels are discussed. Use of highly enriched (57)Fe as target material would lead to formation of high-purity (57)Co

    Cross section measurements of proton induced reactions on 55Mn and comparison of experimental results with different nuclear model calculations

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    Excitation functions of the reactions Mn-55(p,n)Fe-55, Mn-55(p,x)Mn-54 and Mn-55(p,x)Cr-51 were measured from their respective thresholds up to 18 MeV in the first case and up to 45 MeV in the latter two cases, using the conventional stacked-foil technique. The radioactivity of Fe-55 was determined via high resolution X-ray spectrometry; both non-destructively and after radiochemical separation, and of the other radionuclides via high resolution gamma-ray spectrometry. Nuclear model calculations were performed using the codes ALICE-IPPE, EMPIRE and TALYS. In some cases good agreement was found between the experimental and theoretical data while in others considerable deviations were observed. From the experimental data the integral yields of the three investigated radionuclides were calculated

    Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via the (n,p) reaction: Evaluation of excitation function and its validation via integral cross-section measurement using a 14 MeV d(Be) neutron source

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    Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via (n,p) reactions on the target nuclei 32S, 64Zn, 67Zn, 89Y, (90)Zr and 153Eu, respectively, are discussed. The available information on each excitation function was analysed. From the recommended data set for each reaction the average integrated cross section for a standard 14 MeV d(Be) neutron field was deduced. The spectrum-averaged cross section was also measured experimentally. A comparison of the integrated value with the integral measurement served to validate the excitation function within about 15%. A fast neutron source appears to be much more effective than a fission reactor for production of the above-mentioned radionuclides in a no-carrier-added form via the (n,p) process. In particular, the possibility of production of high specific activity 153Sm is discussed
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